Fuel Cycle System Analysis Implications of Sodium-Cooled Metal-Fueled Fast Reactor Transuranic Conversion Ratio

2013 ◽  
Vol 181 (3) ◽  
pp. 427-458
Author(s):  
Steven J. Piet ◽  
Edward A. Hoffman ◽  
Samuel E. Bays ◽  
Gretchen E. Matthern ◽  
Jacob J. Jacobson ◽  
...  
Keyword(s):  
Fast Reactor ◽  
System Analysis ◽  
Fuel Cycle ◽  
Conversion Ratio ◽  
Cycle System

The Screening Methodologies and/or Achievement Evaluation in Japanese FR Cycle Development Program With the Changing Needs for Evaluation

2012 ◽  
Author(s):  
Hiroki Shiotani ◽  
Nariaki Uto ◽  
Koichi Kawaguchi ◽  
Yoshihiko Shinoda ◽  
Kiyoshi Ono ◽  
...  
Keyword(s):  
Phase I ◽  
Phase Ii ◽  
Fast Reactor ◽  
Fuel Cycle ◽  
Development Program ◽  
Development Project ◽  
Performance Criteria ◽  
Main Concept ◽  
Cycle System ◽  
Design Requirements

This paper argues the characteristics evaluation of Fast Reactor and fuel cycle concepts in the FS “Feasibility Study on commercialized fast reactor cycle systems” and the achievement of the performance evaluation conducted in FaCT (Fast Reactor Cycle System Technology Development) project in Japan. At the beginning of FS phase-I (JFY1999), a combinatorial number of candidate concepts with innovative technologies were screened. After the FS phase-I evaluation, the several promising FR cycle concepts were selected to achieve consistency between FR system and fuel cycle system. Analytical evaluation methodologies were developed to compare candidate FR cycle concepts in the FS phase-II (JFY2001 to JFY2005). Finally, the main concepts were decided mainly based on the technical summary (a kind of qualitative evaluation) of FR cycle concepts besides quantitative evaluation in FS phase-II. Sodium cooled FR combined with simplified pelletizing fuel fabrication, and advanced aqueous reprocessing was selected as “main concept” after Japanese government review. In the FaCT phase-I (JFY2006 to JFY2010), the achievement toward the performance criteria / design requirements for the conceptual design of the commercialized facility developed in the FaCT phase-I was also evaluated. However, the objectives of the evaluation were to confirm the direction and the problems of R&D plans, development targets and design requirements. No aggregation methodologies were used in the FaCT final evaluation. Since the design requirements were set as challenges to achieve higher performance, although some items of respective facilities showed an insufficient achievement, a comprehensive evaluation determined that the performance criteria set by the JAEC were achieved in general. The appropriate methodologies to evaluate the total FR and related fuel cycle system varies at different periods, according to our experience in Japanese FR cycle development program. This paper argues the way of methodologies with the changing needs and objectives of evaluation.

scholarly journals Fuel Cycle System Analysis Handbook

2009 ◽  
Author(s):  
Steven J. Piet ◽  
Brent W. Dixon ◽  
Dirk Gombert ◽  
Edward A. Hoffman ◽  
Gretchen E. Matthern ◽  
...  
Keyword(s):  
System Analysis ◽  
Fuel Cycle ◽  
Cycle System

Current Status of the Development of the Fast Reactor Fuel Cycle in India

2009 ◽  
pp. 120-126
Author(s):  
K.V. Govindan Kutty ◽  
P.R. Vasudeva Rao ◽  
Baldev Raj
Keyword(s):  
Fast Reactor ◽  
Fuel Cycle ◽  
Reactor Fuel ◽  
Current Status ◽  
Fast Reactor Fuel

scholarly journals The Effect Assessment for Fast Reactor Fuel Cycle Deployment-improvement of the Assessment Method-

2013 ◽  
Vol 39 ◽  
pp. 43-51
Author(s):  
Kyoko Mukaida ◽  
Hiroki Shiotani ◽  
Kiyoshi Ono ◽  
Takashi Namba
Keyword(s):  
Fast Reactor ◽  
Fuel Cycle ◽  
Assessment Method ◽  
Reactor Fuel ◽  
Effect Assessment ◽  
Fast Reactor Fuel

Comparative Fuel Cycle Analysis of Critical and Subcritical Fast Reactor Transmutation Systems

2003 ◽  
Vol 144 (1) ◽  
pp. 83-106 ◽  
Author(s):  
Edward A. Hoffman ◽  
Weston M. Stacey
Keyword(s):  
Fast Reactor ◽  
Fuel Cycle ◽  
Fuel Cycle Analysis

Physics Studies of Weapons Plutonium Disposition in the Integral Fast Reactor Closed Fuel Cycle

1995 ◽  
Vol 121 (1) ◽  
pp. 17-31 ◽  
Author(s):  
R. N. Hill ◽  
D. C. Wade ◽  
J. R. Liaw ◽  
E. K. Fujita
Keyword(s):  
Fast Reactor ◽  
Fuel Cycle ◽  
Closed Fuel Cycle

Conceptual Study of Neutron Physics of Nuclear Fuel Cycle for Ceramic Fast Reactor

2021 ◽  
Author(s):  
Xuesong Yan ◽  
Yaling Zhang ◽  
Yucui Gao ◽  
Lei Yang
Keyword(s):  
High Temperature ◽  
Nuclear Fuel ◽  
Fast Reactor ◽  
Spent Nuclear Fuel ◽  
Fuel Cycle ◽  
Fission Products ◽  
Nuclear Fuel Cycle ◽  
Purification Method ◽  
Neutron Physics ◽  
Conceptual Study

Abstract To make the nuclear fuel cycle more economical and convenient, as well as prevent nuclear proliferation, the conceptual study of a simple high-temperature dry reprocessing of spent nuclear fuel (SNF) for a ceramic fast reactor is proposed in this paper. This simple high-temperature dry (HT-dry) reprocessing includes the Atomics International Reduction Oxidation (AIROX) process and purification method for rare-earth elements. After removing the part of fission products from SNF by a HT-dry reprocessing without fine separation, the remaining nuclides and some uranium are fabricated into fresh fuel which can be used back to the ceramic fast reactor. Based on the ceramic coolant fast reactor, we studied neutron physics of nuclear fuel cycle which consists operation of ceramic reactor, removing part of fission products from SNF and preparation of fresh fuels for many time. The parameters of the study include effective multiplication factor (Keff), beam density, and nuclide mass for different ways to remove the fission products from SNF. With the increase in burnup time, the trend of increasing 239Pu gradually slows down, and the trend of 235U gradually decreases and become balanced. For multiple removal of part of fission products in the nuclear fuel cycle, the higher the removal, the larger the initial Keff.

scholarly journals Modeling minor actinide multiple recycling in a lead-cooled fast reactor to demonstrate a fuel cycle without long-lived nuclear waste

Nukleonika ◽  
2015 ◽  
Vol 60 (3) ◽  
pp. 581-590 ◽  
Author(s):  
Przemysław Stanisz ◽  
Jerzy Cetnar ◽  
Grażyna Domańska
Keyword(s):  
Nuclear Fuel ◽  
Nuclear Waste ◽  
Fast Reactor ◽  
Fuel Cycle ◽  
Reactor Core ◽  
Nuclear Fuel Cycle ◽  
Minor Actinide ◽  
Closed Nuclear Fuel Cycle ◽  
European Collaboration ◽  
Multiple Recycling

Abstract The concept of closed nuclear fuel cycle seems to be the most promising options for the efficient usage of the nuclear energy resources. However, it can be implemented only in fast breeder reactors of the IVth generation, which are characterized by the fast neutron spectrum. The lead-cooled fast reactor (LFR) was defined and studied on the level of technical design in order to demonstrate its performance and reliability within the European collaboration on ELSY (European Lead-cooled System) and LEADER (Lead-cooled European Advanced Demonstration Reactor) projects. It has been demonstrated that LFR meets the requirements of the closed nuclear fuel cycle, where plutonium and minor actinides (MA) are recycled for reuse, thereby producing no MA waste. In this study, the most promising option was realized when entire Pu + MA material is fully recycled to produce a new batch of fuel without partitioning. This is the concept of a fuel cycle which asymptotically tends to the adiabatic equilibrium, where the concentrations of plutonium and MA at the beginning of the cycle are restored in the subsequent cycle in the combined process of fuel transmutation and cooling, removal of fission products (FPs), and admixture of depleted uranium. In this way, generation of nuclear waste containing radioactive plutonium and MA can be eliminated. The paper shows methodology applied to the LFR equilibrium fuel cycle assessment, which was developed for the Monte Carlo continuous energy burnup (MCB) code, equipped with enhanced modules for material processing and fuel handling. The numerical analysis of the reactor core concerns multiple recycling and recovery of long-lived nuclides and their influence on safety parameters. The paper also presents a general concept of the novel IVth generation breeder reactor with equilibrium fuel and its future role in the management of MA.

Performance of Sodium Natural Circulation Loop for Passvie Decay Heat Removal

2008 ◽  
Author(s):  
Hae-Yong Jeong ◽  
Kwi-Seok Ha ◽  
Won-Pyo Chang ◽  
Yong-Bum Lee ◽  
Dohee Hahn ◽  
...  
Keyword(s):  
Fast Reactor ◽  
System Analysis ◽  
Natural Circulation ◽  
Heat Removal ◽  
Circulation Loop ◽  
Ambient Atmosphere ◽  
Steady State Condition ◽  
Decay Heat ◽  
Natural Circulation Loop ◽  
Test Loop

The Korea Atomic Energy Research Institute (KAERI) is developing a Generation IV sodium-cooled fast reactor design equipped with a passive decay heat removal circuit (PDRC), which is a unique safety system in the design. The performance of the PDRC system is quite important for the safety in a simple system transient and also in an accident condition. In those situations, the heat generated in the core is transported to the ambient atmosphere by natural circulation of the PDRC loop. It is essential to investigate the performance of its heat removal capability through experiments for various operational conditions. Before the main experiments, KAERI is performing numerical studies for an evaluation of the performance of the PDRC system. First, the formation of a stable natural circulation is numerically simulated in a sodium test loop. Further, the performance of its heat removal at a steady state condition and at a transient condition is evaluated with the real design configuration in the KALIMER-600. The MARS-LMR code, which is developed for the system analysis of a liquid metal-cooled fast reactor, is applied to the analysis. In the present study, it is validated that the performance of natural circulation loop is enough to achieve the required passive heat removal for the PDRC. The most optimized modeling methodology is also searched for using various modeling approaches.

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